Tianguo Wei

机构：China General Nuclear Power Corporation (China), Key Laboratory of Nuclear Radiation and Nuclear Energy Technology · ORCID：0000-0002-3845-2147

发表论文 40 篇 · 总被引 937 次 · h-index 14

代表论文

• Microstructure and high-temperature steam oxidation properties of thick Cr coatings prepared by magnetron sputtering for accident tolerant fuel claddings: The role of bias in the deposition process (2019 · Corrosion Science · 被引 153)
• Autoclave grid-to-rod fretting corrosion behaviors of the Zr alloy fuel cladding with and without Cr coating through advanced characterization (2024 · Corrosion Science · 被引 78)
• High-temperature oxidation behavior of Zr-4 and Zr-Sn-Nb alloy in different oxidation ambient (2021 · Journal of Alloys and Compounds · 被引 31)
• The oxidation-dissolution behavior of Cr-coated Zr alloy in high temperature water (2024 · Journal of Nuclear Materials · 被引 20)
• Formation of voids in the Cr coatings with (110)-preferred orientation prepared by arc ion plating under an Au+ irradiation of 20 dpa (2021 · Surface and Coatings Technology · 被引 19)
• Long‐term high‐temperature steam oxidation behavior of Cr‐coated Zircaloy‐4 alloy for accident tolerant fuel (2022 · Materials and Corrosion · 被引 18)